JPS63180896A - Deaerating method of nuclear-reactor water - Google Patents
Deaerating method of nuclear-reactor waterInfo
- Publication number
- JPS63180896A JPS63180896A JP62011272A JP1127287A JPS63180896A JP S63180896 A JPS63180896 A JP S63180896A JP 62011272 A JP62011272 A JP 62011272A JP 1127287 A JP1127287 A JP 1127287A JP S63180896 A JPS63180896 A JP S63180896A
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- nuclear
- water
- reactor water
- gas
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims description 29
- 238000000034 method Methods 0.000 title claims description 6
- 239000007789 gas Substances 0.000 claims description 14
- 238000010438 heat treatment Methods 0.000 claims description 8
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 claims description 4
- 229910001873 dinitrogen Inorganic materials 0.000 claims description 4
- 238000002360 preparation method Methods 0.000 claims description 2
- 241000196324 Embryophyta Species 0.000 description 5
- 238000007872 degassing Methods 0.000 description 5
- 230000005855 radiation Effects 0.000 description 4
- 230000004913 activation Effects 0.000 description 3
- 238000009835 boiling Methods 0.000 description 3
- 239000000941 radioactive substance Substances 0.000 description 3
- 238000005260 corrosion Methods 0.000 description 2
- 230000007797 corrosion Effects 0.000 description 2
- 238000002955 isolation Methods 0.000 description 2
- 239000003795 chemical substances by application Substances 0.000 description 1
- 239000011248 coating agent Substances 0.000 description 1
- 238000000576 coating method Methods 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 238000005336 cracking Methods 0.000 description 1
- 238000010612 desalination reaction Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 238000011144 upstream manufacturing Methods 0.000 description 1
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
Landscapes
- Extraction Or Liquid Replacement (AREA)
Abstract
(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
〔発明の目的〕
（産業上の利用分野）
本発明は、インターナルポンプが用いられている原子炉
における炉水の脱気方法に関する。DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial Application Field) The present invention relates to a method for degassing reactor water in a nuclear reactor in which an internal pump is used.
（従来の技術）
従来の沸騰水型原子炉では、起動時に炉水中の０□濃度
の低減を目的として、タービン系の真空ポンプを用いて
、原子炉を真空状態にした上、装荷燃料による核加熱に
より炉水な昇温し脱気していた。(Prior art) In conventional boiling water reactors, in order to reduce the 0□ concentration in reactor water at startup, a turbine-based vacuum pump is used to create a vacuum state in the reactor, and the nuclear reactor is evacuated by the loaded fuel. The heating caused the reactor water to rise in temperature and degas.
（発明が解決しようとする問題点）
上述した従来の方法では、核加熱に伴い、炉水が放射線
分解され、０□及びＨ２が多量に発生するだけでなく、
放射線の照射により原子炉構造物が放射化されるため、
プラント初期における構造物の酸化被膜中に放射性物質
が取り込まれ、以後の原子炉プラントの放射線源として
後々まで残存する結果となっている。(Problems to be Solved by the Invention) In the conventional method described above, reactor water is radiolyzed with nuclear heating, and not only a large amount of 0□ and H2 is generated, but also
Because nuclear reactor structures are activated by radiation irradiation,
Radioactive substances are incorporated into the oxide coating of structures in the early stages of a plant, and remain as a radiation source in subsequent nuclear reactor plants.
また、炉水中の０２の発生により、脱気効率という観点
からも核加熱が不利となっている。Furthermore, the generation of O2 in the reactor water makes nuclear heating disadvantageous from the viewpoint of deaeration efficiency.
本発明の目的は、核加熱によらず原子炉炉水を昇温させ
て原子炉構造物の放射化を低減させることのできる原子
炉炉水の脱気方法を得ることにある。An object of the present invention is to obtain a method for degassing nuclear reactor water that can reduce the activation of nuclear reactor structures by increasing the temperature of the reactor water without nuclear heating.
（問題点を解決するための手段）
上記目的を達成するために、本発明においては、核加熱
による昇温によらず、原子炉に組込まれたインターナル
ポンプをＮ２ガス加圧下で運転することにより炉水を昇
温し１００℃になった時点で炉水を沸騰脱気させること
を特徴とする原子炉炉水の脱気方法を提供する。(Means for Solving the Problems) In order to achieve the above object, the present invention requires that an internal pump built into a nuclear reactor be operated under N2 gas pressure without relying on temperature increase due to nuclear heating. To provide a method for degassing nuclear reactor water, which is characterized by raising the temperature of reactor water and boiling and degassing the reactor water when the temperature reaches 100°C.
（作用）
このように構成されたものにおいては、Ｎ２ガス加圧下
においてインターナルポンプを運転させることによって
炉水が昇温し、炉水が１００℃に達した時にＮ２ガスを
タービン系に排気させ、これによって炉水が減圧沸騰し
炉水中の０２ガスを脱気させることができる。(Function) With this configuration, the temperature of the reactor water rises by operating the internal pump under N2 gas pressure, and when the reactor water reaches 100°C, the N2 gas is exhausted to the turbine system. As a result, the reactor water is boiled under reduced pressure, and the 02 gas in the reactor water can be degassed.
（実施例）
以下、本発明の一実施例を図面を参照して説明する。図
面において、原子炉圧力容器１内には炉心２が収容され
ており、この原子炉圧力容器１の下部にはインターナル
ポンプ３が設置されている。(Example) Hereinafter, an example of the present invention will be described with reference to the drawings. In the drawing, a reactor core 2 is housed in a reactor pressure vessel 1, and an internal pump 3 is installed in the lower part of the reactor pressure vessel 1.
前記原子炉圧力容器１内で発生した蒸気は原子炉圧力容
器１に接続された主蒸気管４、隔離弁１２を介してター
ビン５に導かれている。このタービン５に導かれた主蒸
気は仕事をした後に復水器６内にて復水となり、給水配
管７に接続された給水ポンプ８、脱塩装置９、給水加熱
器１０を介して再び前記原子炉圧力容器１に導かれる様
になっている。Steam generated within the reactor pressure vessel 1 is guided to the turbine 5 via a main steam pipe 4 connected to the reactor pressure vessel 1 and an isolation valve 12. After the main steam led to the turbine 5 performs work, it becomes condensed water in the condenser 6, and is returned to the above-mentioned state via the water supply pump 8, desalination device 9, and feed water heater 10 connected to the water supply piping 7. It is designed to be guided to the reactor pressure vessel 1.
前記給水加熱器１０の熱源は、前記主蒸気管４からバイ
パスした主蒸気バイパス配管１１から導かれる主蒸気を
用いている。前記復水器６には原子炉圧力容器１内の空
気を脱気させるための真空ポンプ１３が接続されており
、この真空ポンプ１３の下流側は排ガス処理装置１４を
介してスタック１５に遜かれている。また、前記主蒸気
管４の隔離弁１２の上流側には弁１６を介して窒素ガス
供給装置１７が設けられている。The heat source of the feed water heater 10 uses main steam led from a main steam bypass pipe 11 bypassed from the main steam pipe 4. A vacuum pump 13 for deaerating the air in the reactor pressure vessel 1 is connected to the condenser 6, and the downstream side of the vacuum pump 13 is connected to a stack 15 via an exhaust gas treatment device 14. ing. Further, a nitrogen gas supply device 17 is provided on the upstream side of the isolation valve 12 of the main steam pipe 4 via a valve 16 .
以上の構成において、原子炉の起動準備が完了した所で
、原子炉気相部の空気を脱気させるため、タービン５系
の真空ポンプ１３を起動させる。原子炉圧力容器１から
脱気された空気は排ガス処理装置１４を介してスタック
１５へ導き出される。これが終了した所で窒素ガス供給
装置１７よりＮ２ガスを原子炉内へ導き、徐々に原子炉
圧力容器１内を加圧していく。Ｎ２ガスで加圧する理由
は、インターナルボンプ３の定格に近い所で運転するの
に必要なＮＰＳＨが大気圧以下では不足する為である。In the above configuration, when the preparation for starting the reactor is completed, the vacuum pump 13 of the turbine 5 system is started to evacuate the air in the reactor gas phase. Air degassed from the reactor pressure vessel 1 is led to the stack 15 via the exhaust gas treatment device 14. When this is completed, N2 gas is introduced into the reactor from the nitrogen gas supply device 17, and the inside of the reactor pressure vessel 1 is gradually pressurized. The reason for pressurizing with N2 gas is that NPSH, which is necessary to operate at a location close to the internal pump 3's rating, is insufficient below atmospheric pressure.
最終的には原子炉気相部の圧力を４〜５ ｋｇ／ｄに加
圧した状態で、インターナルポンプ３の運転を開始する
。その後インターナルポンプ３の運転による入熱により
炉水は徐々に昇温され、１００℃に達する。Finally, operation of the internal pump 3 is started with the pressure in the reactor gas phase increased to 4 to 5 kg/d. Thereafter, the temperature of the reactor water is gradually raised by heat input due to the operation of the internal pump 3, and reaches 100°C.
炉水が１００℃に達した所で、インターナルポンプ３の
回転数を最小近く迄下げ、更に、気相部のＮ２ガスをタ
ービン５系に排気することにより原子炉内を大気圧近く
まで減圧させる。この時、炉水は減圧沸騰を起こし、同
時に炉水中に含まれている０２ガスは脱気されることと
なる。When the reactor water reaches 100℃, the rotation speed of the internal pump 3 is reduced to near the minimum, and the N2 gas in the gas phase is exhausted to the turbine 5 system, thereby reducing the pressure inside the reactor to near atmospheric pressure. let At this time, the reactor water undergoes boiling under reduced pressure, and at the same time, the 02 gas contained in the reactor water is degassed.
以上の様に核加熱によらない脱気方法を採用することに
より脱気を効率良く行う事が出来るだけでなく、プラン
ト初期に炉心内の放射線による構造物等の放射化を低減
させることから構造物の酸化被膜中に放射性物質が初期
に取り込まれることを防ぐことが可能となる。As mentioned above, by adopting a deaeration method that does not rely on nuclear heating, it is not only possible to perform deaeration efficiently, but also to reduce the activation of structures, etc. due to radiation in the reactor core at the early stage of the plant. It becomes possible to prevent radioactive substances from being incorporated into the oxide film of objects at an early stage.
その結果として、その後の構造物等に起因する放射線源
を減らす事ができ、定検中等の所員等の被曝の低減を図
ることができる。又、脱気によりプラント水環境が改善
される結果、一般腐食、応力腐食割れの発生を抑制する
ことができる。As a result, it is possible to reduce the radiation sources caused by structures, etc., and to reduce the exposure of personnel, etc. during regular inspections, etc. Furthermore, as a result of the deaeration improving the plant water environment, the occurrence of general corrosion and stress corrosion cracking can be suppressed.
本発明によれば、原子炉の起動完了後の脱気方法におい
て、炉水の昇温を核加熱を用いずにインターナルポンプ
の運転による入熱によって行なわせるため、原子炉構造
物の酸化被膜中に放射性物質が取り込まれることがなく
なり原子炉構造物の放射化を低減させることができる。According to the present invention, in the degassing method after the completion of the start-up of a nuclear reactor, the temperature of the reactor water is increased by heat input from the operation of the internal pump without using nuclear heating. Radioactive substances are no longer taken into the reactor structure, and the activation of the reactor structure can be reduced.
図面は本発明の一実施例に用いる原子炉プラントの概略
系統図である。
１・・・原子炉圧力容器 ３・・・インターナルポンプ
１７・・・窒素ガス供給装置
代理人 弁理士 則 近 憲 佑
同 三俣弘文The drawing is a schematic system diagram of a nuclear reactor plant used in an embodiment of the present invention. 1...Reactor pressure vessel 3...Internal pump 17...Nitrogen gas supply system agent Patent attorney Noriyuki Chika Yudo Hirofumi Mitsumata
Claims (1)
空気を脱気させ、その後原子炉内を窒素ガスにて加圧さ
せ、炉水を核加熱させずにインターナルポンプの運転に
よる入熱のみで昇温させ、炉水が１００℃以上になった
場合に原子炉内の窒素ガス及び炉水中の酸素ガスを脱気
させて成ることを特徴とする原子炉炉水の脱気方法。(1) After the reactor startup preparations are completed, the air in the reactor gas phase is degassed, and then the inside of the reactor is pressurized with nitrogen gas, and the internal pumps are operated without nuclear heating of the reactor water. deaeration of reactor water, which is characterized in that the temperature is raised only by heat input from Method.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62011272A JPS63180896A (en) | 1987-01-22 | 1987-01-22 | Deaerating method of nuclear-reactor water |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62011272A JPS63180896A (en) | 1987-01-22 | 1987-01-22 | Deaerating method of nuclear-reactor water |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS63180896A true JPS63180896A (en) | 1988-07-25 |
Family
ID=11773339
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP62011272A Pending JPS63180896A (en) | 1987-01-22 | 1987-01-22 | Deaerating method of nuclear-reactor water |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS63180896A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2018108119A1 (en) * | 2016-12-15 | 2018-06-21 | 深圳中广核工程设计有限公司 | Degassing device and method for gaseous impurities in radioactive waste liquid of reactor of nuclear power plant |
-
1987
- 1987-01-22 JP JP62011272A patent/JPS63180896A/en active Pending
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2018108119A1 (en) * | 2016-12-15 | 2018-06-21 | 深圳中广核工程设计有限公司 | Degassing device and method for gaseous impurities in radioactive waste liquid of reactor of nuclear power plant |
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